Filtered generated 485 hits.
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2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...
Content type: Publications -
2005:36 Reports within the Area of Nuclear Power Plant Instrumentation
Bengt-Göran Bergdahl SKI English...
Content type: Publications -
2006:30 Benchmarking – a validation of UTDefect
Jonas Niklasson, Anders Boström, Håkan Wirdelius SKI English...
Content type: Publications -
2006:10 Models for MOX fuel behaviour - A selective review
Ali R. Massih SKI English...
Content type: Publications -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile stresses are present as well as a material were SCC can occur, SCC could potentially be a problem for the...
Content type: Publications -
2005:58 The Swedish Concept for Disposal of Spent Nuclear Fuel: Differences Between Vertical and Horizontal Waste Canister Emplacement
D. G. Bennett, T. W. Hicks SKI English...
Content type: Publications -
2003:29 Long-term Integrity of the KBS-3 Engineered Barrier System
SKI English...
Content type: Publications -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Content type: Publications -
2005:55 Application of Master Curve Methodology for Structural Integrity Assessments of Nuclear Components
Iradj Sattari-Far, Kim Wallin SKI English...
Content type: Publications -
SSMFS English
About the regulations in English Some of the Swedish Radiation Safety Authority’s regulations (SSMFS) are available in English. The translations are unofficial versions of the Authority’s regulations. In the event of any discrepancy between the Swedish and English versions, the Swedish original will take precedence. The Authority's regulations in Swedish...